ML20245J284
| ML20245J284 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/23/1989 |
| From: | Liaw B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245J293 | List: |
| References | |
| NUDOCS 8906300262 | |
| Download: ML20245J284 (5) | |
Text
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i UNITED STATES
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- NUCLEAR REGULATORY. COMMISSION -
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1 l TENNESSEE' VALLEY AUTHORITY DOCKET NO. 50-327 i
SEQUOYAH hUCLEAR' PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission).has-.found that:
A.
The 6pplication for amendment by Tennessee Valley Authority-(the
-licensee)'datedJune~16,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations' set forth.in 10 CFR Chapter I; B.
The ffcility will operate in conformity with the application, the provisions of the Act, and the rules and' regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in complidnce with the Commission.'s regulations;
.D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8906300262 890623 PDR ADOCK 05000327 p
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Accordingly, the license-is amended by changes-to the Technical Specifications as indicated in the attachment to this license amendment ano paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as.
revised through Amendment No.118, are hereby incorporated in the
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' license.
The licensee shall. operate the facility in accordance with the Technical Specifications..
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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D. l'aw, Director T(VA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 23, 1989 l
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v-ATTACHMENT TO LICENSE AMENDMENT NO. 118 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Sper,ifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by-the captioned amendment number and contain marginal lines. indicating the area of. change.
Overleaf pages* are provided to
' maintain document completeness.
REMOVE INSERT-q 3/4 1-17 3/4'l-17 3/4 1-17a
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' REACTIVITY-CONTROL SYSTEMS POSITION INDICATI0N' SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The' shutdown'.and control rod position indication system and the demand position indication system 'shall be OPERABLE and capable of determining the control rod positions withir i 12 steps.
APPLICABILITY:
MODES l'and 2.
ACTION:
i With a maximum of one rod position indicator per bank inoperable:
a.
either:
- 1. # Determine the position of the non-indicating rod (s) indirectly by the movable incore' detectors at least once per'8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rod which exceeds'24 steps in one directio'n since the last determination-of the rod's position, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, b.
With a maximum of one demand position indicator per bankLinoperable
.either:
1.
Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least
. withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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For the remainder of the Unit 1 Cycle 4, Action a.1 will be superceded by the following, for shutdown rod position indicators only:
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Initially determine the position of the non-indicating rod (s) indirectly by the moveable incore detectors and, at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, verify by alternate methods that the non-indicating rod (s) have not moved.
If there is indication that the subject rod (s) may have moved, then immediately
. initiate action to determine the new position (by the moveable incore detectors) of any non-indicating rod (s) that have moved since the last determination of the rod (s) position.
The provisions of 3.0.4 are not applicable for Action a.1 for the remainder of Unit 1 Cycle 4.
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l SEQUOYAH - UNIT 1 3/4 1-17 Amendment No. 118
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' REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM - OPERATING SURVEILLANCE REQUIREMENTS 4.1.3.2
. verifying. that. the demand position indication system and the indication system agree within 12 steps at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position' Deviation Monitor is-inoperable, then~ compare the demand position indication system and the rod position indica-
. tion system at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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i SEQUOYAH - UNIT 1 3/4 1-17a Amendment No.118
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